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The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
David Weitzel, Youho Lee (Univ of New Mexico), Michael Short (MIT), Michael Laufer (Kairos Power), Sam Sham (ANL)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1176-1182
Much progress has recently been made on Molten Salt Reactor (MSR) technology with the strategic support of the Department of Energy (DOE). However, concerns regarding the structural material’s compatibility with the salt have hampered the detailed design and evaluation of reliability and economics. Existing research also neglects fluid flow when measuring alloy dissolution. FLiBe flow affects species diffusion through the salt and in turn modifies the reaction kinetics at the alloy surface. Without a proper understanding of the flow effects on alloy dissolution, MSR performance assessments will inevitably remain imprecise.
This research entails the construction of a subscale molten salt loop to test the effects of FLiBe flow on the corrosion rate of various alloys. Our test loop will consist of a molten salt pump connected to a bimetallic composite test loop with a sample holder for the tested alloys. The salt temperature and velocity can be varied independently to replicate the varied operating conditions in the MSR and better characterize the effects of FLiBe flow on corrosion. Investigating the effects of salt flow on alloy element dissolution will advance material choice for key reactor components. These findings will enable nuclear engineers to create more detailed and accurate plant designs.